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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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New laws offer nuclear industry incentives for existing power plant uprates
This year, the U.S. nuclear industry received a much-needed economic boost that could help preserve operating nuclear power plants and incentivize upgrades that extend their lifespan and power output.
Signed into law in 2022, the Inflation Reduction Act offers production tax credits (PTCs) for existing nuclear power plants and either PTCs or investment tax credits (ITCs) for new carbon-free generation. These credits could make power uprates—increasing the maximum power level at which a commercial plant may operate—a much more appealing option for utilities.
V. C. Boffi, F. Premuda
Nuclear Science and Engineering | Volume 38 | Number 3 | December 1969 | Pages 205-215
Technical Paper | doi.org/10.13182/NSE69-A21155
Articles are hosted by Taylor and Francis Online.
A two energy group model is proposed in this paper for studying the criticality of a slab of finite thickness in the framework of neutron transport theory. The system of the two stationary Boltzmann equations which, in the case of isotropic scattering, govern the flux distributions of the two neutron groups, is first solved by a Fourier transform technique. Explicit series expressions are then derived for the angular as well as for the total flux distributions in the interior and at the boundary of the critical slab. These series expressions are shown by numerical calculations to be rapidly convergent to the required solutions of the problem under examination. Results for the critical parameter and for the total and angular flux distributions are at last reported.